Letter Sequence Supplement |
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Results
Other: ML20147C490, ML20149E859, ML20151B320, ML20155D675, ML20197B030, ML20199B161, ML20204F596, ML20210R060, ML20211B406, ML20211B442, ML20212H574, ML20212H582, ML20214E205, ML20214L960, ML20215H383, ML20215H397, ML20234F422, ML20235R405, ML20235R426, ML20236D305, ML20236D319, ML20236P920, ML20245E060, ML20245E067
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MONTHYEARML20211B4421985-12-31031 December 1985 Annual Radiological Environ Operating Rept for 1985 Project stage: Other ML20155D6751985-12-31031 December 1985 Annual Nonradiological Environ Monitoring Rept,1985 Project stage: Other ML20210R0601986-02-24024 February 1986 Staff Assessment of Environ Radioactive Contamination in Vicinity of Rancho Seco Nuclear Power Plant Project stage: Other ML20214E2051986-03-0303 March 1986 Forwards Semiannual Radioactive Effluent Release Rept,Jul- Dec 1985. Changes to Offsite Dose Calculation Manual, Process Control Program & Rept Corrections Included. Operational & environmentally-related Events Discussed Project stage: Other ML20214L9801986-04-0101 April 1986 Summary of 860325 Meeting W/Epa Re Offsite Contamination Problems & Requirements of 40CFR190 Project stage: Meeting ML20197B0301986-04-30030 April 1986 Informs That Util Will Submit Completed 1985 Annual Radiological Environ Operating Rept by 860530.Delay Due to Difficulties in Completing Liquid Effluent Pathway Land Use Census Project stage: Other ML20211B4061986-05-27027 May 1986 Forwards 1985 Annual Radiological Environ Operating Rept, Including Parts I & II of Environ Radiological Studies Downstream from Rancho Seco Nuclear Power Generating Station - 1985 Project stage: Other ML20199B1611986-06-0505 June 1986 Special Rept 86-08 Re Max Hypothetically Exposed Individual Surpassing Numerical Guides for Design Objectives of 10CFR50,App I.More Appropriate Modeling Techniques Encl. Offsite Dose Calculation Manual Revised Project stage: Other ML20204F5961986-07-0303 July 1986 Responds to NRC Re Violation Noted in Insp Rept 50-312/86-15.Corrective Actions:Util Will Submit Amend to Tech Spec Table 4.21-1 Re Radioactive Liquid Waste Sampling Prior to Startup Project stage: Other ML20212G1351986-07-22022 July 1986 Advises That Changes to Radiological Effluent Tech Specs Should Be Proposed to Eliminate Possibility of Unacceptable Radiation Levels in Liquid Effluents.Evaluation of 860224 Rept Encl.Meeting Requested Project stage: Meeting ML20214L9601986-08-29029 August 1986 Forwards Documentation Summarizing NRC Actions to Close Out Offsite Contamination Issue,In Response to 860325 Request Project stage: Other ML20055C2251986-09-30030 September 1986 Responds to NRC 860718 Request for Addl Info Re Plant Liquid Effluents.Requested Info Will Be Provided by End of Nov 1986 Due to Magnitude of Effort Required Project stage: Request ML20245E0671986-12-0202 December 1986 Forwards Util Response to 860718 Inquiry Into Operations & Mgt of Plant Liquid Effluent Program.Util Considers That Discharge of Radioactive Matl in Liquid Effluents Allowable by Tech Specs within Limits of 10CFR20,App B Project stage: Other ML20245E0601987-01-0505 January 1987 Forwards Revs to Util 861202 Response to NRC Liquid Effluent Inquiry for Clarification,Per 861222 Discussion W/R Meeks Project stage: Other ML20212H5821987-01-12012 January 1987 Radiological Effluent Release & Radiological Environ Operating Repts for 1984,Rancho Seco Nuclear Generating Station, Technical Evaluation Rept Project stage: Other ML20212H5741987-01-16016 January 1987 Forwards TER-C5506-657, Radiological Effluent Release & Radiological Environ Monitoring Operating Repts for 1984, Rancho Seco Nuclear Generating Station, Technical Evaluation Rept Project stage: Other ML20245E0631987-02-19019 February 1987 Forwards Response to NRC 861224 Request for Addl Info Re Inquiry Into Operations & Mgt of Plant Liquid Effluent Program.Response Completes Util Efforts to Provide Requested Info Project stage: Request ML20205S8181987-02-25025 February 1987 Notification of 870303 Meeting W/Util in Bethesda,Md to Review Discrepancies in Plant Liquid Effluent Program & to Discuss Changes to Tech Specs & Offsite Dose Calculation Manual to Correct Identified Discrepancies Project stage: Meeting ML20197D4831987-04-0707 April 1987 Summary of 870303 Meeting W/Util in Bethesda,Md Re Problems Identified W/Facility Liquid Effluent Program & Proposed Corrective Actions.Attendance List Encl Project stage: Meeting ML20215H3831987-04-15015 April 1987 Forwards Rev 1 to Procedure R-0775, Facility Change Safety Analysis. Design Bases of Current Mod to Secondary Waste Water Sys Not Intended to Be Equivalent to Evaporation Ponds Described in Submittal Project stage: Other ML20215H3971987-04-15015 April 1987 Rev 1 to Procedure R-0775, Facility Change Safety Analysis Project stage: Other ML20209C7401987-04-20020 April 1987 Confirms Commitments Made During 870303 Meeting W/Nrc in Bethesda,Md Re Radiological Liquid Effluent Matters.Dose Based Surveillance Std Appropriate for Ensuring Compliance w/10CFR50,App I Regulation.List of Commitments Encl Project stage: Meeting ML20235F7541987-06-30030 June 1987 Application for Amend to License DPR-54,consisting of Amend 155,revising Tech Specs Re Radiological Effluents to Ensure Compliance W/Regulatory Requirements Concerning Effluent Monitoring & Nearby Land Use Identification.Fee Paid Project stage: Request ML20235R4261987-10-0303 October 1987 Proposed Radiological Effluent Tech Specs,Incorporating Clarifications & Correcting Editorial Errors Project stage: Other ML20235R4051987-10-0303 October 1987 Rev 1 to Proposed Amend 155,revising Radiological Effluent Tech Specs to Incorporate Clarifications & Correct Editorial Errors Project stage: Other ML20236D3191987-10-0707 October 1987 Rev 0 to Radiological Environ Monitoring Program Manual Project stage: Other ML20236D3051987-10-20020 October 1987 Forwards Rev 0 to Radiological Environ Monitoring Program Manual, for Review in Support Evaluation of Proposed Amend 155 to License DPR-54 Project stage: Other ML20236P9201987-11-12012 November 1987 Forwards Radioactive Liquid Effluent Sys Description Including P&Id,Design Criteria,Instrumentation & Control Measures to Support Evaluation of Proposed Amend 155 Project stage: Other ML20149E8591987-12-22022 December 1987 Proposed Tech Specs,Establishing New Set Lower Limits of Detection for Prebatch Release & Composite post-release Analyses Project stage: Other ML20149E8521987-12-23023 December 1987 Supplemental Application for Amend to License DPR-54, Consisting of Rev 2 to Proposed Amend 155,establishing New Set of Lower Limits of Detection for Prebatch Release & Composite post-release Analyses Project stage: Supplement ML20234F4221987-12-27027 December 1987 Forwards Rev 5 to AP.310, Offsite Dose Calculation Manual, for Review to Support Evaluation of Proposed Amend 155, Rev 2.Rev Incorporates Results of Verification & Validation as Well as NRC & Internal Reviews Project stage: Other ML20147C4901988-01-0505 January 1988 Forwards Fr Notice of Consideration of Issuance of Amend to License DPR-54 & Proposed NSHC & Opportunity for Hearing on 870630 Request Re Revs to Radiological Effluent Tech Specs Project stage: Other ML20149E2561988-01-0707 January 1988 Forwards Supplemental Info to Radioactive Liquid Effluent Sys Description Provided Via Ltr Gca 87-763 Dtd 871112,to Support Evaluation of Rev 2 to Proposed Amend 155.Concerns Raised Re Radioactive Liquid Effluent Sys Listed Project stage: Supplement ML20148J8111988-03-17017 March 1988 Forwards Amend 98 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs,Reducing Lower Limits of Detection for Liquid Radioactive Effluents & Changing Requirements to Address Hardware Changes in Effluent Sys Project stage: Approval ML20151B3201988-03-30030 March 1988 Forwards Errata to Amends 97 & 98 to License DPR-54, Correcting Inadvertent Errors in Tech Specs Project stage: Other 1987-10-20
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20236E8211998-06-0303 June 1998 Forwards Insp Rept 50-312/98-02 on 980519-21 & NOV Re Failure to Review & Consider All Info Obtained During Background Investigation.Areas Examined During Insp Also Included Portions of Physical Security Program ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 IR 05000312/19980011998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-01 on 980205 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202C4641998-02-0505 February 1998 Forwards Insp Rept 50-312/98-01 on 980105-08 & Notice of Violation.Insp Included Decommissioning & Dismantlement Work Underway,Verification of Compliance W/Selected TS & Main & Surveillance Activities Associated W/Sfp ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20198K5391997-10-21021 October 1997 Forwards Insp Rept 50-312/97-04 on 970922-25 & Notice of Violation.Response Required & Will Be Used to Determine If Further Action Will Be Necessary ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20198G8141997-08-22022 August 1997 Forwards Amend 125 to License DPR-54 & Safety Evaluation. Amend Permits Smud to Change TS to Incorporate Revised 10CFR20.Amend Also Revises References from NRC Region V to NRC Region IV ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 ML20149E5031997-07-10010 July 1997 Second Partial Response to FOIA Request for Documents. Forwards Records Listed in App C Being Made Available in Pdr.Records in App D Already Available in PDR ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141A1721997-06-17017 June 1997 Forwards Insp Rept 50-312/97-03 on 970603-05.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program 1999-08-31
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 NL-97-030, Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs1997-05-13013 May 1997 Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs ML20138F5321997-04-28028 April 1997 Forwards Response to RAI Re License Amend 192,updating Cask Drop Design Basis Analysis,Per NRC 960510 Request for Addl Info on 960318 Application NL-97-027, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-04-17017 April 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility ML20137W8091997-03-20020 March 1997 Forwards Biennial Update to Rancho Seco Post-Shutdown Decommissioning Activities Rept ML20137S3571997-03-19019 March 1997 Provides Notification of Use of Revised Quality Manual for Activities Re Rancho Seco ISFSI ML20137D0981997-03-18018 March 1997 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1996.Provided IAW TS D6.9.2.2 & Guidance Contained in NRC Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1996 ML20137D1221997-03-18018 March 1997 Submits,Iaw 10CFR20.2206 & TS D6.9.2.1,1996 NRC Form 5 Individual Monitoring Repts for Personnel Requiring Radiation Exposure Monitoring Per 10CFR20.1502 During 1996. W/O Encl NL-97-012, Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3)1997-02-11011 February 1997 Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3) ML20138L1091997-01-29029 January 1997 Informs of Schedule Change Re Decommissioning of Rancho Seco.Incremental Decommissioning Action Plan,Encl NL-97-005, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-01-22022 January 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility NL-96-056, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1996-12-16016 December 1996 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20134E0041996-10-23023 October 1996 Forwards Response to NRC GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks ML18102B6871996-08-0606 August 1996 Informs That Util Will Revise Loading & Unloading Procedures & Operator Training as Necessary ML20149E4491994-05-16016 May 1994 Forwards 1993 Annual Rept of Sacramento Municipal Utility District,For Info ML20149E3971994-05-10010 May 1994 Forwards Re Updated Decommissioning Cost Estimate for Rancho Seco & Attached Rept by Tlg Engineering,Inc. W/Svc List ML20059H6731994-01-20020 January 1994 Forwards Revised Rancho Seco Quality Manual, Reflecting Current Rancho Seco Pol Phase Nuclear Organization Changes ML20059E1221994-01-0303 January 1994 Forwards Amend 7 to Long Term Defueled Condition Physical Security Plan.Encl Withheld (Ref 10CFR73) ML20059C1681993-12-22022 December 1993 Forwards Suppl Info to Support Review & Approval of 930514 Proposed License Amend 186 Re Nuclear Organization Changes, Per NRC Request 1999-07-07
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5431990-09-20020 September 1990 Requests Exemptions from Certain Requirements of 10CFR50.47(b) & 50,App E & Proposes New Emergency Plan That Specifically Applies to Long Term Defueled Condition ML20059J9161990-09-13013 September 1990 Notification of Change in Operator/Senior Operator Status for R Groehler,Effective 900907 ML20059J9221990-09-13013 September 1990 Responds to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2,Part 2, 'Vendor Interface for Safety-Related Components.' No Vendor Interface Exists for Spent Fuel Pool Liner NL-90-442, Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-2121990-09-12012 September 1990 Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-212 ML20059G0791990-09-0606 September 1990 Forwards Supplemental Fitness for Duty Performance Data, Omitted from 900725 Rept Re Random Drug Testing Results ML20059E0031990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept,Jan- June 1990, Corrected Repts & Revs to ODCM ML20059C2491990-08-27027 August 1990 Advises That M Foster & B Rausch Leaving Util Effective on 900810 & 17,respectively & Will No Longer Require Active Operator Licenses ML20056B2591990-08-20020 August 1990 Forwards Long-Term Defueled Condition Security Training & Qualification Plan. Encl Withheld (Ref 10CFR2.790) ML20056B2961990-08-10010 August 1990 Discusses 900731 Meeting Re Future of Util & Closure & Decommissioning of Facility.Request for Possession Only License Pending Before Commission ML20058Q2811990-08-0909 August 1990 Forwards Updated Listing of Commitments & long-range Scope List Items Deferred or Closed by Commitment Mgt Review Group Since Last Update ML20058N0911990-08-0707 August 1990 Notifies of Minor Change in List of Tech Specs Applicable in Plant Defueled Condition.Determined That Surveillance Requirements Table 4.1-1,Item 63 Not Required to Be Included in List of Tech Specs Applicable in Defueled Condition ML20056A1131990-07-30030 July 1990 Apprises of Status of Plans to Use 3 of 4 Emergency Diesel Generators as Peaking Power Supplies & Responds to Questions in .Util Obtained Authorization for Operation of Diesel Generators for No More than 90 Days Per Yr ML20056A2041990-07-30030 July 1990 Provides Response to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. Pressure & Differential Pressure Transmitters 1153 & 1154 Do Not Perform Any safety-related Function in Current Plant Mode ML20055J0311990-07-25025 July 1990 Forwards fitness-for-duty Performance Data for Facility from 900103-0630 ML20055J0331990-07-25025 July 1990 Notifies of Change in Operator/Senior Operator Status. Operators Terminating Employment & No Longer Require License ML20055H8081990-07-24024 July 1990 Forwards Decommissioning Financial Plan for Plant,Per 10CFR50.33(k)(2) & Requests Interim Exemption Re Requirement to Have Full Decommissioning Funding at Time of Termination of Operation,Per 10CFR50.12 ML20055H7561990-07-24024 July 1990 Requests Exemption from Performing Annual Exercise of Emergency Plan,Activation of Alert & Notification Sys & Distribution of Public Info Brochures,Per 10CFR50.12 Requirements ML20055F8421990-07-13013 July 1990 Forwards Application for Proposed Decommissioning of Plant. Util Needs Relief from Equipment Maint,Surveillance,Staffing & Other Requirements Not Necessary to Protect Public Health & Safety During Defueled Condition ML20055G9821990-07-12012 July 1990 Advises That Environ Exposure Controls Action Plan Will Be Provided by Sept 1990,per Insp Rept 50-312/90-02 ML20055E5111990-07-0606 July 1990 Notifies of Change in Operator/Senior Operator Status for D Rosenbaum & M Cooper,Effective 900622 & 29,respectively ML20055C3541990-02-14014 February 1990 Forwards Updated Response to Insp Rept 50-312/88-30. Calculations for Liquid Effluent Monitors Completed & in Use & Rev to Reg Guide 4.15 in Procedure RSAP-1702 Scheduled to Be Completed & Implemented by Apr 1990 ML20055C3511990-02-14014 February 1990 Forwards Addl Info Re 900306 Response to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latching Relays Mfg by Ge. Util Will Replace Only Relays Found Not to Meet Insp Criteria ML20248H2571989-10-0606 October 1989 Responds to NRC Re Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54 Re Reactor Vessel Vent Valve Testing.No Testing of Reactor Vessel Vent Valves Will Be Performed ML20248H2391989-10-0606 October 1989 Requests Exemption from Requirements of 10CFR26 Re Fitness for Duty Programs Based on Present & Future Operational Configuration ML20248A8271989-09-25025 September 1989 Requests Permission to Submit Next Amend to Updated FSAR W/Decommissioning Plan Submittal.Extension Will Allow District to Incorporate Plant Closure Status in SAR Update to Reflect Plant Conditions Accurately ML20248D4611989-09-13013 September 1989 Responds to 890906 Request for Assessment of Util Compliance W/Ol & Associated Programs & Commitments,Per 10CFR50.54(f). Staffing Requirements for Emergency Preparedness Will Not Be Violated & Future Shortfalls Will Be Remedied ML20247G1991989-09-11011 September 1989 Requests Extension for Time Period Equivalent to That of Current Shutdown.Extension Would Result in Revised Final Expiration Date of Not Earlier than 900318.Plant Would Not Be Brought Above Cold Shutdown W/O NRC Prior Concurrence ML20247H3551989-09-0707 September 1989 Informs That Util Stands by Commitments of 890621 & 0829 Re Implementation of Closure Plan in Safe & Deliberate Manner in Compliance W/License & W/All Applicable Laws & Regulations ML20247H5541989-09-0101 September 1989 Responds to Violations Noted in Insp Rept 50-312/89-14. Corrective Actions:Stop Order on Fuel Movement Issued & Action Plan Generated on 890908 to Address Broader Issues 05000312/LER-1988-010, Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys1989-08-23023 August 1989 Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys ML20246A4011989-08-16016 August 1989 Forwards Rev 5 to Inservice Testing Program Plan. Changes Identified Consistent W/Guidance Provided by Generic Ltr 89-04 NL-89-593, Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request1989-08-15015 August 1989 Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request ML20245H4781989-08-10010 August 1989 Requests Exemption from Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs Because on 890607,util Board of Directors Ordered That Plant Cease Operation ML20245H1781989-08-0909 August 1989 Notifies of Change in Operator/Senior Operator Status. J Dailey & J Reynolds Terminated Employment on 890721 & 890802,respectively ML20245L1831989-08-0808 August 1989 Informs That Official Correspondence Must Be Directed to Listed Individuals Due to Reorganization of Util Following 890606 Election ML20247L9221989-07-26026 July 1989 Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-312/88-33.Corrective Action:Portable Shield Walls Inspected Every 6 Months to Ensure All Safety Factors Met & Area Surveys Conducted on Weekly Basis ML20247M4121989-07-24024 July 1989 Requests Exemption from 10CFR50,App E,Section IV.F.2 to Allow Util Not to Perform Annual Emergency Plan Exercise for 1989.Request Results from Transitional Mode of Plant from Operating Plant to Plant Preparing for Decommissioning NL-89-541, Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 8912151989-07-14014 July 1989 Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 891215 ML20246P4011989-07-14014 July 1989 Informs That Evaluation of Contracts & Agreements Identified No Restrictions on Employee Ability to Provide Info About Potential Safety Issues to NRC NL-89-547, Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 1061989-07-0606 July 1989 Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 106 ML20246A9751989-06-30030 June 1989 Advises That Concerns Addressed in Generic Ltr 89-08 Inapplicable,Since Util Intends to Defuel Reactor.Generic Ltr Will Be Reviewed Prior to Placing Facility in heatup-cooldown Operational Mode for Return to Power ML20246A5171989-06-30030 June 1989 Forwards Rancho Seco Closure Plan, Per 890621 Request for Addl Info Re Plan CEO-89-289, Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date1989-06-27027 June 1989 Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date NL-89-526, Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl1989-06-22022 June 1989 Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl ML20245H4181989-06-21021 June 1989 Discusses Util Plans Re Overall Closure of Plant,Per 890615 Meeting W/Nrc.Util Will Request Appropriate Changes to Tech Specs to Reflect Defueled Mode & Will Evaluate & Request Changes to Emergency Plan ML20245D9281989-06-21021 June 1989 Discusses Activities Underway Re Plan for Closure of Plant Discussed During 890615 Meeting W/Region V.Util Intends to Continue Use of Essential Programs,Such as Preventive Maint Program,For Sys within Scope of Closure Process ML20245A0981989-06-16016 June 1989 Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. No Westinghouse Plugs Used at Plant ML20248B5751989-06-0202 June 1989 Advises That Util Anticipates That Final Analysis of Thermal Striping Will Conservatively Support Surge Line Lifetime Significantly Longer than June 1994 Date,Per NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification NL-89-468, Submits Justification for Absence of Functional Testing Requirement in Proposed Tech Spec 4.14(f) Re Snubber Svc Life Monitoring,Per 890517 Request1989-05-30030 May 1989 Submits Justification for Absence of Functional Testing Requirement in Proposed Tech Spec 4.14(f) Re Snubber Svc Life Monitoring,Per 890517 Request ML20247N2601989-05-25025 May 1989 Requests Guidance Re Whether NRC Concurs W/Arbitrator Order Concerning Employee Access to Plant 1990-09-06
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$SMUD SACRAMENTO MUNICIPAL UT!LITY DISTRICT D 6201 S Street, P.O. Box 15800, Sacramento CA 95852-1830,(916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JAN 0 71988 GCA 87-916 U.S. Nuclear Regulatory Commission Attn: Frank J. Miraglia, Jr.
Associate Director for Projects Philips Building 7920 Norfolk avenue Bethesda, MD 20014 backet No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 RADI0 ACTIVE LIQUID EFFLUENT SYSTEMS DESCRIPTION SUPPLEMENT
Dear Mr. Miraglia:
The District hereby submits supplemental information to the Radioactive Liquid Effluent Systems Description, which was provided to you via letter GCA 87-763 dated 11/12/87, to support the evaluation of Proposed Amendment No.155, Revision 2. The supplemental information presented in Attachment I represents action items identified during the 11/13/87 radiological effluent meeting between tiie District and the NRC at Rancho Seco.
Concerns raised in regards to the Radioactive Liquid Effluent Systems Description and responded to in Attachment I include:
- 1. Adequacy of the effluent strainer for catching expected resin firas.
- 2. Design information comparison between expected resin fines size and strainer size.
- 3. Effect of the filters at the radiation monitor inlets on monitor l readings.
l 4. Effect of sunlight on demineralizer hoses.
! 5. Consideration of radiological aspects of skid mounted equipment l outside the Auxiliary Building.
) 6. Adequacy of snap fittings on the Demineralizer.
6801130270 880107 PDR P ADOCK 05000312 PDR
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i RANCHO SECO NUCLEAR GENERATING STATION D 1444o Twin Cities Road Herald, CA 95638-9799;(209) 333 2935
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GCA 87-916 Frank J. Miraglia, Jr. # N 0 7 1988 Please contact me if have any questions. Members of your staff with questions requiring additional information or clarification may contact Mr. Richard Mannheimer at (209) 333-2935.
Sincerely,
/ Ojn*
G. Carl Andognini Chief Executive Officer, 1 Nuclear Attachment cc: G. Kalman, NRC, Bethesda (w/atch)
A. D'Angelo, NRC, Rancho Seco ( " )
C. Willis, NRC, Bethesda (
)
J.B. . Martin, NRC, Region V ( )
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ATTACHMENT 1 RADI0 ACTIVE LIQUID EFFLUENT SYSTEM DESCRIPTION SUPPLEMENT l
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Attachment 1 1 of 9 ACTION ITEM 1:
PROVIDE DESIGN INFORMATION ON EXPECTED SIZE OF RESIN WHICH WILL BE CAUGHT BY EFFLUENT STRAINER PROCESSING. COMPARE WITH HISTORICAL DATA ON RESIN FINES FOUND IN PLANT EFFLUENTS.
RESPONSE
SMUD specifications for commercial grade secondary side domineralizer resin require that the amount of resin passing through a 40 mesh screen be limited to 1.5% of the resin volume. According to resin suppliers contacted, the volure of subsize resin beads beyond 40 mesh decreases rapidly with increasing mesh size (see attached graph). Pass-through at 50 mesh typically can be as low as 0.5%, and at 100 mesh (140 microns) no pass-through of resin particles is expected. No typical particle size distributions are available beyond 50 mesh since particle size distributions vary with manufacturer, type of resin, ,
and batch number.
Fractured beads, which are commonly found in reprocessed or regenerated resin, are not considered to reach the Effluent Strainer since the Sluiceable i Demineralizer beds will be operated in the throw-away mode and be loaded with strong, high crush strength resin. Resin fines in the potentially radioactive process stream from either the 'A' or 'B' RHU1 c3n be removed by the Sluiceable Demineralizer inlet filter which has a Vari 3hle "Scention capability down to 3 microns. The Sluiceable Demineralizer is also followed by a 100 mesh Y-strainer. Both of these filters (pre-filter and af ter-filter), which are associated with the Sluiceable Denineralizer, can prevent resin fines from reaching the effluent Strainer.
Sample analyses of creek sediment have not identified the presence of resin i fines. Find.ags from creek surveys are contained in Lawrence Livermore Lab reports issued to SMUD in 1985,1986, and 1987. SMUD has no historical data 1 on resin fines found in plant effluents or the Retention Basins. Lawrence Livermore Lab
- verbally verified they had seen resin beads in the Retention Rasins, but no resin fines and no dccumentation on the quantity of resin beads exists. Operational changer in Condensate Polishing Demineralizer beds to no regeneration during periods of secondary side contamination, and the directing of all liquids from the Polishing Sump Demineralizers through the Effluent Strainer via the Regenerant Hold-up Tank protect against possible release of radioactively contaminated resin fines into the plant effluent.
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- Basin samples taken by LLNL on S/23/84 and 8/16/84 Reference LLNL Report UCID-20298, pg. No. 4, pg. No.11.
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FIGURE FOR RESPONSE TO ACTION ITDI 1 ATTACHMENT 1
. 2 of e 100-90-80-W E 70 D
.J h FINES : SUBSIZE BEADS g 60- )
<t 1. 5 '/o 0F TOTAL VOLUME IS GREATER o THAN 40 MESH AS SPECIFIED E
& 50-u.
o H 40-2 w I U
$ 30- ;
- c. -
50 %
4 5 */.
20-10-3.5 % l.0 % 0.5 %
0 10 20 30 40 5O 60 7'o 8'O 90 ido MESH I I I I 830 420 220 14 0 RESIN VOLUME DISTRIBUTION BY RESIN BEAD SIZE l 1
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(1) SMUD PO RN 87 21744 !
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Attachment 1 3 of 9 RESPONSE: (ACTION ITEM 1 CONTINUED)
Makeup Demineralizer regeneration waste released via the Regenerant Holdup Tank (RHUT C) into the plant effluent may contain non-radioactively contaminated resin fines. These resin fines, when exposed to the potentially radioactively contaminated discharge from the 'A' and 'B' RHUTs, may become radioactively contaminated. The radioactivity level of these resin fines will
, be directly proportional to the radioactivity of the effluent stream. Since I
the radioactivity level of the effluent can range from zero to very low, depending on the source of water, the time average radioactivity concentration of resin fines is not likely to exceed the highest radioactivity levels encountered in the wastewater.
Attachment 1 4 of 9 ACTION ITEM 2:
PROVIDE DESIGN INFORMATION ON STRAINER SIZE OF EFFLUENT DEMINERALIZER.
COMPARE WITH EXPECTED SIZE OF EFFLUENT DEMINERALIZER RESINS / RESIN FINES.
RESPONSE
The plant Effluent Strainer, which is valved to operate and backvash in parallel, consists of 6 tubular filter modules. Current filter elements are 100 mesh (140 microns) 316 SS woven screens which match the particle retention capability of the Sluiceable Demineralizer Y-Strainer that precedes the Effluent Stainer. The retention capability of the Effluent Strainer therefore is considered acceptable because resin fines are not expected to pass through a 100 mesh screen (see response to Action Item 1).
/ttachment 1 5 of 9 ACTION ITEM 3:
PROVIDE DESIGN INFORMATION ON THE EFFECT OF FILTERS AT RADIATION MONITOR INLETS ON THE VALIDITY OF MONITOR READINGS.
RESPONSE
l The three radiatian monitors R-15020, R15017A and R-150178 monitor the Radioactive Liquic Effluent releases. Only two of the three radiation monitors, R-15017A and R-15017B, use a strainer in the sample inlet. Approval of Proposed Amendn nt No.155, Rev. 2 will change the Technical Specification monitor from R-15010 to R-15017A.
A duplex manually bat \ washable strainer is used to renove gross debrir and prevent the monitor f'iow meter from clogging. The strainer element >pening and surface area are 890 microns and 241 square inches, respectively. The elements are selected to ensure that a representative sample is obt.ined. The large openir.gs in the strainer ensure that radioactive material is not retained on the strainer. The element surface area is large enouca to provide at least 10 days of continuous operation between backwashes. Duplex strainer configuration allows uninterrupte6 radiation monitor operation dtring backwashes.
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Attachment 1 6 of 9 ACTION ITEM 4:
PROVIDE DESIGN INFORMATION ON EFFECT OF SUNLIGHT ON DEMINERALIZER H0SES.
RESPONSE
H(ses used for process fluid consist of an inner tube and an external, reinforced, braided stainless steel wire hose. The outer surface is wrapped with fabric tape to protect the metal braiding. The pressure boundary material of the demineralizer hose, ethylene propylene diene (EPDM), is not exposed to sunlight. The external surface of the hose material is rated as "Excellent" against weathering, sunlight, heat, and "Outstanding" against exposure.
The pressure rating of the hose is 250 psig, while the maximum operating pressure at pump shut-off is approximately 100 psig. The hoses were hydrotested at the factory at 1.5 times the rated pressure.
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Attachment 1 7 of 9 ACTION ITEM 5:
PROVIDE DESIGN INFORMATION ON CONSIDERATION OF RADIOLOGICAL ASPECTS OF SKID MOUNTED EQUIPMENT OUTSIDE THE AUXILIARY BUILDING. EVALUATE FAILURE MODES, BERM AND DRAIN SIZING, AND FLOWPATHS. COMPARE RADIOLOGICAL PROTECTIVE i
MEASURES T0 THOSE DESCRIDED IN THE USAR.
RESPONSE
The design modification to the secondary waste system considers potential radioactive contamination. Since the modification included equipment that could concentrate the potential contamination, measures beyond those considered in the original secondary waste system design are implemented.
Among the measures implemented are the following:
. A curb to contain spills and decon water.
. A drain and sump system to collect and redirect spills, i
. A decon facility for equipment washdown.
The skid mounted strainer and demineralizer are within a curbed area which has '
, a retention capacity of 2,000 gallons. This volume is considered more than
- adequate to contain any upset or leakage of approximately 50 gpm. The Sluiceable Demineralizer and Effluent Strainer are monitored periodically while the syster, is operating. Pipe or hose failures would be contained ,
through valve operations.
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- The drain and sump subsystems can collect leakage or spilled water and pump it i
back to the 'A' or #B' RHUT. This system is designed at 50 gpm which is equivalent to the failure of a 1 1/2 inch line. !
A decon facility for washdown of demineralizer resin casks prior to shipment
- is provided. This washdown water, at approximately 20 gpm, is directed to the drain and sump subsystems.
i Shielding of the strainer and demineralizer is not considered necessary due to i the low levels of potential contamination.
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Attachment 1
- 3 8 of 9 RESPONSE: (ACTION ITEM 5 CONTINUED) l i
Since the liquid processed in this subsystem contains only the secondary side drains and leakages, design considerations beyond those employed for the RHUTs are only appropriate for the equipment with concentrating _ capability. The Miscellaneous Liquid Radwaste System, located inside the Auxiliary Building, processes primary side liquids with radioactivity orders of magnitude greater than those in the Radioactiv, Liquid Effluent System. The performance ,
objectives of the Radioactive Liquid Effluent System are the same as those for the Miscellaneous Liquid Radwaste System. As stated in Chapter 11 of the USAR, the systems are designed to reasonably assure that plant personnel and the general public are protected against excessive exposure from radioactive liquid wastes in accordance with limits defined in 10CFR20,10CFR50, and 40CFR190.
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Attachment 1 9 of 9 ACTION ITEM 6:
PROVIDE DESIGN INFORMATION ON ADEQUACY OF SNAP FITTINGS ON DEMINERALIZER.
RESPONSE
Hose couplings in process flow lines (1 1/2") are of the cam 1cck type and are rated at 250 psig. The maximum operating pressure is approximately 100 psig.
The cem lock type coJplings have been used for over five years by Pacific Nuclear (the sJpplier of our Sluiceable Demineralizer) in radwaste applications without any problems. These fittings and the hoses are used in low level radwaste domineralizers, radwaste solidification, and resin transfer systems.
The 1/2" vent and sample lines are provided with Swagelok connectors which are rated at 750 psig.
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